Detailed activation, decay heat and waste disposal calculations of the ARIE
S-AT design are performed to evaluate the safety aspects of the device. The
high initial activity of the SiC highly irradiated components translates d
irectly into a higher initial decay heat for these structures than for the
well-protected steel-based components. However, after a one-hour cool-down
period, the SiC decay heat drops by two decades to levels comparable to the
steel-based components. The decay heat of the LiPb coolant was found to ex
ceed that of the SiC components for several days after shutdown. This impli
es that a loss of flow accident (LOFA) event is more critical than a loss o
f coolant accident (LOCA) event for LiPb/SiC systems. Regarding waste dispo
sal, all structures can easily meet the Class C Low-Level Waste (LLW) requi
rements established for the ARIES power plants. Many components could quali
fy as Class A LLW after a 100-year storage period after selection of low ac
tivation materials and control of the Nb and Mo impurities in ferritic stee
l. A purification system will be required to remove the Po-210 and Hg-203 g
enerated by Pb during operation.